US11289223B2 - Power plant chemical control system - Google Patents

Power plant chemical control system Download PDF

Info

Publication number
US11289223B2
US11289223B2 US16/089,774 US201716089774A US11289223B2 US 11289223 B2 US11289223 B2 US 11289223B2 US 201716089774 A US201716089774 A US 201716089774A US 11289223 B2 US11289223 B2 US 11289223B2
Authority
US
United States
Prior art keywords
coolant
sensor
flow
throttling device
power plant
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
US16/089,774
Other languages
English (en)
Other versions
US20200381132A1 (en
Inventor
Vladimir Georgievich KRITSKIY
Nikolay Aleksandrovich PROKHOROV
Fedor Vladimirovich NIKOLAEV
Pavel Semenovich STYAZHKIN
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Science and Innovations JSC
Atomproekt JSC
Original Assignee
Science and Innovations JSC
Atomproekt JSC
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Science and Innovations JSC, Atomproekt JSC filed Critical Science and Innovations JSC
Assigned to Joint Stock Company Scientific Research and Design Institute for Energy Technologies Atomproekt, JOINT STOCK COMPANY "SCIENCE AND INNOVATIONS" reassignment Joint Stock Company Scientific Research and Design Institute for Energy Technologies Atomproekt ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: KRITSKIY, Vladimir Georgievich, NIKOLAEV, Fedor Vladimirovich, PROKHOROV, Nikolay Aleksandrovich, STYAZHKIN, Pavel Semenovich
Publication of US20200381132A1 publication Critical patent/US20200381132A1/en
Application granted granted Critical
Publication of US11289223B2 publication Critical patent/US11289223B2/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N17/00—Investigating resistance of materials to the weather, to corrosion, or to light
    • G01N17/02—Electrochemical measuring systems for weathering, corrosion or corrosion-protection measurement
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to power engineering, in particular, to process control devices for ensuring reliable operation of the power plant equipment using process circuit water chemistry control means.
  • Power plants including nuclear power plants (NPPs) with water-cooled reactors, relate to highly technical and complex facilities. Given that the energy source at these facilities is a controlled nuclear fission reaction, closer attention is paid to assurance of safe and reliable operation of such power plants. Maintenance of the required water quality of the primary and secondary circuits of nuclear power plants is one of essential conditions ensuring safe, reliable and cost-efficient operation of NPPs (refer to NP-001-15 “General Safety Provisions for Nuclear Power Plants” at https://www.seogan.ru/np-001-15). Chemical control systems are designed to ensure receipt of the latest information about the water chemistry condition based on the measurements of the rated and diagnostic parameters of the process circuit aqueous media.
  • Management of water chemistry quality indices is based on the data received from the chemical control systems.
  • the scope or composition of the measured quality indices shall ensure receipt of sufficient information for relevant assessments of the current process circuit water chemistry condition and the corrosion of the equipment in these circuits.
  • the collection, processing, archiving and display of the chemical control data shall be ensured by the system-level application of modern hardware and software products.
  • STO 1.1.1.03.004.0980-2014 Water Chemistry of the Primary Circuit during Commissioning of the Nuclear Power Plant Unit under AES-2006 Project. Coolant Quality Standards and Supporting Means”.
  • STO1.1.1.03.004.0979-2014 Water Chemistry of the Secondary Circuit during Commissioning of the Nuclear Power Plant Unit under AES-2006 Project. Working Medium Quality Standards and Supporting Means” at http://www.snti.ru/snips_rd3.htm).
  • a system for monitoring and protecting pipelines against corrosion including a pipeline; two to eight independent control channels, each containing a corrosion rate sensor comprising a corrosion measuring transducer and a sensor interface device; and an actuator for inhibitor injection comprising a dispenser and a dispenser interface device; wherein a microcontroller is integrated into each channel of the system connected to the device designed for control, processing and storage of information by a computer.
  • the disadvantage of the disclosed system is its failure to ensure reliable operation of power plants, for example, for the primary and secondary circuits with water-cooled water-moderated power reactors (VVER type reactors) and pressurized water reactors (PWRs) at the design power, in transient modes or in cleaning, passivation and outage modes.
  • VVER type reactors water-cooled water-moderated power reactors
  • PWRs pressurized water reactors
  • the system does not take into account any essential differences in the parameters of the filling medium conditions and process circuit hydraulic characteristics, even within the same power plant, as compared to any pipeline route.
  • a chemical control system for the coolant of a water-cooled reactor is disclosed (refer to JP2581833, IPC G01N 17/02, published on Feb. 12, 1997), including an electrochemical potential sensor installed in the coolant and connected to a potentiostat with its output further connected to a computer equipped with a memory unit and a monitor.
  • the computer is connected to an actuator for gas or chemical reagent injection.
  • the disadvantage of the disclosed system is arrangement of sensors in the active evaporation area, as well as directly in the neutron field.
  • many materials including elements of insulating materials and conductor wires of the sensors, when exposed to neutrons, change their physical and mechanical properties.
  • the period of reliable operation of sensors of the disclosed system is clearly less than that in the neutron field compared to the duration of operation of similar equipment beyond its limits, and sensors may be replaced only during the shutdown of the power unit for refueling.
  • the measured values especially the concentrations of dissolved gases, will fluctuate to a great extent.
  • a power plant chemical control system is disclosed, which coincides with this engineering solution in the maximum number of essential features and is accepted as a prototype (EP0661538, IPC G01N 17/02, G21C 17/02, published on Jul. 5, 1995).
  • the prototype system includes installation of a coolant electrochemical indication sensor in the reactor core and its connection for corrosion potential calculation to the measuring data processing and transmission unit with its output connected to the central computer system operating the actuator for hydrogen and chemical reagents injection.
  • the system may also include a dissolved oxygen sensor, a hydrogen peroxide sensor, an electrical conductivity sensor, and a pH sensor.
  • the disadvantage of the disclosed system is that under the conditions of a powerful radiation field of the reactor core, the duration of operation of sensors and system elements is less compared to the duration of operation of similar equipment beyond its limits, and replacement of sensors and system elements is possible only during power unit shutdown for refueling. All elements of the system are to be replaced due to high induced activity, including electrodes of the polarization resistance sensor. At the same time, regular updating of the sensor surface state when changing them reduces the reliability of the predictive estimates of corrosion wear, since the overall corrosion decreases over time along the parabola, while corrosion properties of the medium remain unchanged.
  • the objective of this engineering solution is to develop such a power plant chemical control system that would ensure a longer service life of the sensors while maintaining reliable values of the rated and diagnostic parameters of the water media in process circuits at power, transient modes or in cleaning, passivation and outage modes.
  • the power plant chemical control system includes at least one coolant electrochemical indication sensor electrically connected to the measurement data processing and transmission unit, with its output connected to a central programmable controller for the actuator for injection of hydrogen and chemical reagents.
  • the coolant electrochemical indication sensor is of a flow type, its hydraulic input is connected by a sampling tube to the process circuit of the power plant, and its hydraulic output is hydraulically connected to the first heat exchanger and the first throttling device with a reversible coolant supply circuit in series.
  • the sample coolant passing through the sensor is discharge into the drain line through the first heat exchanger to reduce the coolant temperature and the throttling device to reduce pressure and flow rate.
  • the throttling device is provided with a reversible coolant supply circuit that maintains a constant flow rate of the sample through the coolant electrochemical indication sensor.
  • the reverse circuit is especially important when the reactor is operated in transient modes (start-up, shutdown), when the power unit capacity is changed, including emergency trips. Changes in the reactor/boiler unit power or switching of the pumps are accompanied by an increase in the coolant of suspended insoluble particles of corrosion products forming the surface loose and poorly adherent to the dense protective oxide films deposits under stationary conditions.
  • the reversible circuit in these cases ensures maintenance of the constant sample flow through electrochemical sensors, which ensures receipt of reliable values of rated and diagnostic parameters of the aqueous media in the process circuits.
  • the coolant electrochemical indication sensor may be made in the form of a flow-type sensor of the polarization resistance.
  • the coolant electrochemical indication sensor may be made in the form of a flow-type sensor of the electrochemical potential.
  • the coolant electrochemical indication sensor may be installed in the primary process circuit of the power plant.
  • the working coolant electrochemical indicator sensor may be installed in the secondary process circuit of the power plant.
  • the chemical control system of the power plant may include a dissolved oxygen sensor, and/or a dissolved hydrogen sensor, and/or an electrical conductivity sensor, and/or a pH sensor mounted between the second heat exchanger hydraulically connected to the process circuit of the power plant and the second throttling device or the installed after the throttling device.
  • the coolant electrochemical indication sensors of this chemical control system of the power plant can be installed in the process circuits of various power plants: circulation circuits of boiling-type reactors, such as BWR (boiling water reactor) and RBMK (high power channel reactor), in the primary and secondary circuits of the NPPs with PWR and VVER reactors, in the circuits of thermal stations.
  • circulation circuits of boiling-type reactors such as BWR (boiling water reactor) and RBMK (high power channel reactor
  • BWR boiling water reactor
  • RBMK high power channel reactor
  • the power plant chemical control system of the primary circuit of a pressurized light-water reactor is considered below.
  • FIG. 1 shows a hydraulic circuit diagram of the primary circuit of the pressurized light-water reactor with the power plant chemical control system
  • FIG. 2 shows an electric circuit diagram of the power plant chemical control system
  • FIG. 3 shows a circuit diagram of the throttling device with a reversible coolant supply circuit.
  • the primary circuit of the power plant with a chemical control system (refer to FIG. 1 ) consists of a reactor pressure vessel ( 1 ) with a pressurizer ( 2 ), the primary circulation circuit equipment, including pipeline ( 3 ) for the heated coolant supply to the steam generator ( 4 ) and its return through the pipeline ( 5 ), the main circulation pump ( 6 ) through the pipeline ( 7 ) to the reactor pressure vessel ( 1 ).
  • the system for controlling and maintaining the primary circuit water chemistry quality includes an outlet ( 8 ) and an inlet pipelines ( 9 ) connecting the reactor pressure vessel ( 1 ) to the equipment of the blowdown and makeup systems consisting of a regenerative heat exchanger ( 10 ), a coolant purification system on ion-exchange filters ( 11 ), and a make-up pump ( 12 ).
  • the reactor pressure vessel ( 1 ) is hydraulically connected by a sampling tube ( 13 ) to the flow-type sensor ( 14 ) for the coolant electrochemical indication, for example, comprising a polarization resistance sensor “S 1 ” ( 15 ) and an electrochemical potential sensor “S 2 ” ( 16 ) that are hydraulically connected in series with the first heat exchanger ( 17 ) and the first throttling device ( 18 ) with a reversible coolant supply circuit ( 19 ).
  • S 1 ( 15 ) and S 2 ( 16 ) may be connected in series (as shown in FIG. 1 ) or in parallel, depending on their structure and operating conditions.
  • the first throttling device ( 18 ) can be made in the form of a housing with inlet and outlet nozzles, wherein a set of throttling orifices is installed (not shown in the drawing).
  • the hydraulic outlet of the first throttling device ( 18 ) is connected to the first drain line ( 20 ).
  • the flow-type sensor “S 1 ” ( 15 ) of the polarization resistance and the flow-type sensor “S 2 ” ( 16 ) of the coolant electrochemical indication of the unit ( 14 ) (refer to FIG.
  • the CPC ( 22 ) is equipped with a monitor ( 25 ) for visual control of the measurement data by the operator and making of managerial decisions during the power unit operation.
  • the chemical control system of the power plant may include (refer to FIG.
  • S 3 ( 26 ), S 4 ( 27 ), S 5 ( 28 ) and S 6 ( 29 ) may be connected in parallel (as shown in FIG. 1 ) or in series, depending on their structure and operating conditions.
  • the inlet of the second heat exchanger ( 30 ) can be hydraulically connected to the reactor pressure vessel ( 1 ) by removal from the tube ( 13 ) (one entry point) or by a sampling tube ( 32 ) (two entry points, as shown in FIG. 1 ).
  • the second drain line ( 33 ) is designed for coolant samples passing through S 3 ( 26 ), S 4 ( 27 ), S 5 ( 28 ) and S 6 ( 29 ).
  • S 3 ( 26 ), S 4 ( 27 ), S 5 ( 28 ) and S 6 ( 29 ) are electrically connected (refer to FIG. 2 ) to the second measurement data processing and transmission unit “U 2 ” ( 34 ), the outlet of the U 2 ( 34 ) is connected to the central computer ( 22 ).
  • FIG. 3 shows the first throttling device ( 18 ) with more detailed picture of the reversible coolant supply circuit ( 19 ).
  • the reversible circuit ( 19 ) contains tubes ( 35 , 36 ) for the reversible coolant sample supply and valves ( 37 , 38 , 39 , 40 ) ensuring the reverse flow of the sample through the first throttling device ( 18 ).
  • the valves 37 and 38 are open and valves 39 and 40 are closed.
  • the reverse flow of the sample through the first throttling device ( 17 ) during its flushing occurs if valves 37 and 38 are closed and valves 39 and 40 are open.
  • the primary circuit coolant is automatically fed from the standard sampling points through the tube ( 13 ) to the set ( 14 ) of flow-type sensors for the electrochemical indication of the coolant containing, for example, S 1 ( 15 ) for polarization resistance and S 2 ( 16 ) for electrochemical potential; then the sample flow passes the first heat exchanger ( 17 ) and the first throttling device ( 18 ) with a reversible coolant supply circuit ( 19 ) for cleaning of the throttling device ( 18 ).
  • the first heat exchanger ( 17 ) and the first throttling device ( 18 ) provide optimum values for the temperature, pressure and flow rate of the sample into the drain line ( 20 ).
  • the signals from S 1 ( 15 ) and S 2 ( 16 ) are sent to the measurement data processing and transmitting unit U 1 ( 21 ) and further to the CPC ( 22 ).
  • the working medium is fed through tube 32 (in one process connection option) or through tube 13 (in another process connection option) to the second heat exchanger ( 30 ) and passes at room temperature through S 3 ( 26 ), S 4 ( 27 ), S 5 ( 28 ) and S 6 ( 29 ) measuring the rated and diagnostic parameters related to the quality of the process circuit medium.
  • the sample flow then passes through the second throttling device ( 31 ) and enters the drain line ( 33 ).
  • the signals from S 3 ( 26 ), S 4 ( 27 ), S 5 ( 28 ) and S 6 ( 29 ) are sent to U 2 ( 34 ) and then to the CPC ( 22 ).
  • the processed measurement results of S ( 15 ), S 2 ( 16 ), S 3 ( 26 ), S 4 ( 27 ), S 5 ( 28 ) and S 6 ( 29 ) are used to justify management decisions during power unit operation.
  • the inner surfaces of the first throttling device ( 18 ) are cleaned from the iron corrosion products that are slightly adherent to the surface by changing the direction of the sample flow using valves 37 , 38 , 39 , 40 of the reversible circuit ( 19 ).
  • the production prototype of the corrosion monitoring complex was mounted on one of the power units with RBMK-1000 reactor (high-power channel-type reactors).
  • the power unit with RBMK-1000 reactor is a single-circuit power plant of a boiling type.
  • the coolant is light water (H 2 O) moving along the multiple forced circulation circuit connecting the channel-type reactor, the turbine and the main circulation pump.
  • the circuit diagram of the multiple forced circulation circuit is similar to that shown in FIG. 1 (items 1 , 4 , 6 ).
  • Organization of automatic sampling and supply of the sample to the power plant chemical control system are also similar (refer to FIG. 1 , items 13 , 16 - 20 ).
  • the first option of the chemical control system production prototype configuration consisted of a cell with electrodes of an electrochemical potential sensor, a heat exchanger/cooler, a throttling device as a set of throttle orifices.
  • the set of throttle orifices was designed to provide a pressure drop from 8 to 0.15 MPa and to maintain the coolant sample flow rate at about 20 dm 3 /h.
  • the electrochemical potential was measured using a typical measuring transducer and 4-20 mA signal tapping to the recording system on the typical recording chart.
  • the coolant sample flow through the complex reduced by half (up to 10 dm 3 /h) after 200 hours and to 3 dm 3 /h after 800 hours, which corresponds to an extension in the transport lag time by six times, up to approximately 5 minutes, with the sampling tube length of 10 meters from the sampling point to the sensor.
  • the extended transport lag time has a negative effect on the reliability of the values of the rated and diagnostic parameters of the process circuit water media.
  • the coolant sample flow rate of (17-19) dm 3 /h was restored as a result of the following procedures: disconnection of the complex from the multiple forced circulation circuit, removal of a set of throttling orifices from the complex, mechanical removal of iron corrosion products deposits from the internal surfaces of the set of throttling orifices, assembly of the set of throttling orifices, installation of the set of throttling orifices in the hydraulic circuit of the complex and its commissioning. Regular monitoring of the sample flow rate showed that the flow rate is gradually decreasing at almost the same rate as at the beginning of the test.
  • Quality indicators changed during the start-up and shutdown periods within the following limits: from 25 to 140 ⁇ g/kg for oxygen concentration; from 0 to 4 ⁇ g/kg for hydrogen concentration; from 20 to 100 ⁇ g/kg for iron corrosion products concentration; from 0.28 to 0.77 ⁇ S/cm for the specific electrical conductivity. Timely switching of the coolant flow direction through the throttling device allowed to maintain the flow rate within the limits from 15 to 18 dm 3 /h acceptable for measurement reliability.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Health & Medical Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Environmental Sciences (AREA)
  • Biodiversity & Conservation Biology (AREA)
  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • Ecology (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Feeding, Discharge, Calcimining, Fusing, And Gas-Generation Devices (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)
  • Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
US16/089,774 2017-06-30 2017-06-30 Power plant chemical control system Active US11289223B2 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/RU2017/000473 WO2019004856A1 (ru) 2017-06-30 2017-06-30 Система химического контроля энергетической установки

Publications (2)

Publication Number Publication Date
US20200381132A1 US20200381132A1 (en) 2020-12-03
US11289223B2 true US11289223B2 (en) 2022-03-29

Family

ID=63364135

Family Applications (1)

Application Number Title Priority Date Filing Date
US16/089,774 Active US11289223B2 (en) 2017-06-30 2017-06-30 Power plant chemical control system

Country Status (12)

Country Link
US (1) US11289223B2 (ar)
EP (1) EP3648112B1 (ar)
JP (1) JP6802857B2 (ar)
KR (1) KR20200024065A (ar)
CN (1) CN109429524B (ar)
AR (1) AR113233A1 (ar)
CA (1) CA3019058C (ar)
EA (1) EA039710B1 (ar)
HU (1) HUE058934T2 (ar)
JO (1) JOP20180065A1 (ar)
RU (1) RU2696819C1 (ar)
WO (1) WO2019004856A1 (ar)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2019164584A2 (en) 2017-12-29 2019-08-29 Nuscale Power, Llc Controlling a nuclear reaction
CN111551482B (zh) * 2020-05-15 2022-03-25 中国核动力研究设计院 高温高压一、二回路联动运行的综合动水腐蚀试验装置
RU2761441C1 (ru) * 2020-12-30 2021-12-08 Акционерное Общество "Атомэнергопроект" Система фильтрации потока теплоносителя бака-приямка системы аварийного охлаждения активной зоны
RU2759318C1 (ru) * 2021-03-11 2021-11-11 Федеральное государственное унитарное предприятие "Научно-исследовательский технологический институт имени А.П. Александрова" Способ контроля содержания радионуклидов йода в теплоносителе водо-водяных ядерных энергетических установок
CN113393950B (zh) * 2021-04-21 2022-08-19 华能山东石岛湾核电有限公司 一种核电厂辅助电锅炉功率调节方法

Citations (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3956063A (en) * 1971-05-28 1976-05-11 The United States Of America As Represented By The United States Energy Research And Development Administration Emergency core cooling system for a fast reactor
US4138320A (en) * 1978-06-29 1979-02-06 The United States Of America As Represented By The United States Department Of Energy Fluidic self-actuating control assembly
EP0417571A1 (en) 1989-09-11 1991-03-20 Hitachi, Ltd. System and electrode for "in situ" monitoring the quality of high temperature water in power plants
US5323429A (en) * 1993-01-15 1994-06-21 Westinghouse Electric Corporation Electrochemical monitoring of vessel penetrations
US5579354A (en) * 1993-12-20 1996-11-26 Hitachi, Ltd. Method of measuring a corrosion potential, method of simulating potential characteristics of a reaction rate, and plant monitoring system adopting them
US20070017822A1 (en) * 2004-03-26 2007-01-25 Baker Hughes Incorporated General and localized corrosion rate measurements
RU2326372C1 (ru) 2006-11-16 2008-06-10 Федеральное государственное унитарное предприятие "Государственный научный центр Российской Федерации-Научно-исследовательский институт атомных реакторов" Способ определения массовой концентрации кислорода в контурах под давлением с водным теплоносителем
US20080283418A1 (en) * 2004-03-26 2008-11-20 Baker Hughes Incorporated Quantitative Transient Analysis of Localized Corrosion
CN101477843A (zh) * 2008-12-30 2009-07-08 中国科学院金属研究所 高温高压水循环系统
US20090184003A1 (en) * 2008-01-23 2009-07-23 Baker Hughes Incorporated Localized Corrosion Monitoring Device for Limited Conductivity Fluids
US20110209730A1 (en) * 2008-12-03 2011-09-01 Varrin Jr Robert D Chemical Cleaning Method and System with Steam Injection
US20120279874A1 (en) * 2010-11-04 2012-11-08 Schlumberger Technology Corporation Electrochemical ph measurement
US20130153473A1 (en) * 2010-10-15 2013-06-20 Diversified Technologies Services, Inc. Concentrate treatment system
US20130182808A1 (en) * 2007-11-15 2013-07-18 The State of OR acting by and through the State Board of Higher Education on behalf of OR State Un Stable startup system for a nuclear reactor
US8797021B2 (en) * 2011-02-14 2014-08-05 Ge-Hitachi Nuclear Energy Americas Llc Electrochemical corrosion potential probe assembly

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4978506A (en) * 1988-05-18 1990-12-18 Westinghouse Electric Corp. Corrosion product monitoring method and system
JP2523900B2 (ja) * 1989-11-01 1996-08-14 株式会社日立製作所 センサ―、原子炉、原子炉の制御方法、及びセンサ―の製造方法
JPH0592798A (ja) * 1991-10-03 1993-04-16 Taisei Corp 浮遊体の水平移動抑止方法
RU2120143C1 (ru) * 1998-03-26 1998-10-10 Анискин Юрий Николаевич Способ организации водно-химического режима
US7111458B2 (en) * 2003-07-11 2006-09-26 Sauer-Danfoss Inc. Electrical loop flushing system
US9689856B2 (en) * 2015-04-10 2017-06-27 Electric Power Research Institute Non-destructive methods for noble metal loading analysis on material surfaces

Patent Citations (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3956063A (en) * 1971-05-28 1976-05-11 The United States Of America As Represented By The United States Energy Research And Development Administration Emergency core cooling system for a fast reactor
US4138320A (en) * 1978-06-29 1979-02-06 The United States Of America As Represented By The United States Department Of Energy Fluidic self-actuating control assembly
EP0417571A1 (en) 1989-09-11 1991-03-20 Hitachi, Ltd. System and electrode for "in situ" monitoring the quality of high temperature water in power plants
US5203984A (en) * 1989-09-11 1993-04-20 Hitachi, Ltd. Monitoring system for plant operation condition and its in-situ electrochemical electrode
US5323429A (en) * 1993-01-15 1994-06-21 Westinghouse Electric Corporation Electrochemical monitoring of vessel penetrations
US5579354A (en) * 1993-12-20 1996-11-26 Hitachi, Ltd. Method of measuring a corrosion potential, method of simulating potential characteristics of a reaction rate, and plant monitoring system adopting them
US20080283418A1 (en) * 2004-03-26 2008-11-20 Baker Hughes Incorporated Quantitative Transient Analysis of Localized Corrosion
US20070017822A1 (en) * 2004-03-26 2007-01-25 Baker Hughes Incorporated General and localized corrosion rate measurements
RU2326372C1 (ru) 2006-11-16 2008-06-10 Федеральное государственное унитарное предприятие "Государственный научный центр Российской Федерации-Научно-исследовательский институт атомных реакторов" Способ определения массовой концентрации кислорода в контурах под давлением с водным теплоносителем
US20130182808A1 (en) * 2007-11-15 2013-07-18 The State of OR acting by and through the State Board of Higher Education on behalf of OR State Un Stable startup system for a nuclear reactor
US20090184003A1 (en) * 2008-01-23 2009-07-23 Baker Hughes Incorporated Localized Corrosion Monitoring Device for Limited Conductivity Fluids
US20110209730A1 (en) * 2008-12-03 2011-09-01 Varrin Jr Robert D Chemical Cleaning Method and System with Steam Injection
CN101477843A (zh) * 2008-12-30 2009-07-08 中国科学院金属研究所 高温高压水循环系统
US20130153473A1 (en) * 2010-10-15 2013-06-20 Diversified Technologies Services, Inc. Concentrate treatment system
US20120279874A1 (en) * 2010-11-04 2012-11-08 Schlumberger Technology Corporation Electrochemical ph measurement
US8797021B2 (en) * 2011-02-14 2014-08-05 Ge-Hitachi Nuclear Energy Americas Llc Electrochemical corrosion potential probe assembly

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
"Actuator" Wikipedia, Way Back Machine Internet Archive entry for http://en.wikipedia.org/wiki/Actuator on Feb. 9, 2017, https://web.archive.org/web/20170209073923/https://en.wikipedia.org/wiki/Actuator (last accessed Oct. 19, 2021) (4 pages).
Kuang et al. (CN 101477843 A, machine translation). (Year: 2009). *

Also Published As

Publication number Publication date
CN109429524B (zh) 2022-10-14
EP3648112B1 (en) 2022-02-16
RU2696819C1 (ru) 2019-08-06
KR20200024065A (ko) 2020-03-06
AR113233A1 (es) 2020-02-19
HUE058934T2 (hu) 2022-09-28
CA3019058C (en) 2021-11-09
EA039710B1 (ru) 2022-03-03
JOP20180065A1 (ar) 2019-01-30
US20200381132A1 (en) 2020-12-03
CA3019058A1 (en) 2018-12-30
JP6802857B2 (ja) 2020-12-23
BR112018069995A2 (pt) 2020-01-21
CN109429524A (zh) 2019-03-05
EA201992879A1 (ru) 2020-04-21
WO2019004856A1 (ru) 2019-01-03
JP2020514675A (ja) 2020-05-21
EP3648112A1 (en) 2020-05-06

Similar Documents

Publication Publication Date Title
US11289223B2 (en) Power plant chemical control system
Moan et al. Leak-before-break in the pressure tubes of CANDU reactors
EP2073217B1 (en) Chemical injection system and chemical delivery process/method of injecting into an operating power reactor
Snead et al. Severe accident test station design document
Rempe et al. TMI-2-A Case Study for PWR Instrumentation Performance during a Severe Accident
JP5634007B2 (ja) 原子炉運転方法および運転停止後原子炉の放射線レベル低減方法
EP1794760B1 (en) Device and method for the determination of the electrochemical corrosion potential
Tapping Corrosion issues in pressurized heavy water reactor (PHWR/CANDU®) systems
BR112018069995B1 (pt) Sistema de controle químico de instalação energética
Osterhout Operation of the water-to-sodium leak detection system at the experimental breeder reactor II
CN211788199U (zh) 一种核电站堆芯测量系统及核电站控制系统
JP4722026B2 (ja) 原子力発電プラントの水素注入方法
TWI403700B (zh) 用於沸水式反應爐之水位決定方法
Babu et al. Proposed modernization and refurbishment of instrumentation and control systems of the FBTR and Kamini reactors in India
Manzer Transport mechanisms of uranium released to the coolant from fuel defects
Byers et al. WATCH Loop Development and Commissioning Tests
Chocron et al. Actions concerning nuclear power plant life evaluation
Langman et al. Recent CANDU transient fuel behaviour data from research reactor irradiations
Plummer Reactor materials inspection by neutron radiography
Guzonas et al. Strategies for corrosion monitoring and control in a CANDU®-SCWR
Turner et al. Improving chemistry performance in CANDU plants
Ofstun et al. Westinghouse-GOTHIC modeling of the Wolf Creek RCS draindown event
Plummer COMPONENT REQUIREMENTS AND METHODS
Cll E'f3"-l0ev
Thompson 100 Area Process Water Pressure Decay Test Program: Part 1

Legal Events

Date Code Title Description
FEPP Fee payment procedure

Free format text: ENTITY STATUS SET TO UNDISCOUNTED (ORIGINAL EVENT CODE: BIG.); ENTITY STATUS OF PATENT OWNER: LARGE ENTITY

AS Assignment

Owner name: JOINT STOCK COMPANY SCIENTIFIC RESEARCH AND DESIGN INSTITUTE FOR ENERGY TECHNOLOGIES ATOMPROEKT, RUSSIAN FEDERATION

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNORS:KRITSKIY, VLADIMIR GEORGIEVICH;PROKHOROV, NIKOLAY ALEKSANDROVICH;NIKOLAEV, FEDOR VLADIMIROVICH;AND OTHERS;REEL/FRAME:048092/0986

Effective date: 20181112

Owner name: JOINT STOCK COMPANY "SCIENCE AND INNOVATIONS", RUSSIAN FEDERATION

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNORS:KRITSKIY, VLADIMIR GEORGIEVICH;PROKHOROV, NIKOLAY ALEKSANDROVICH;NIKOLAEV, FEDOR VLADIMIROVICH;AND OTHERS;REEL/FRAME:048092/0986

Effective date: 20181112

STPP Information on status: patent application and granting procedure in general

Free format text: DOCKETED NEW CASE - READY FOR EXAMINATION

STPP Information on status: patent application and granting procedure in general

Free format text: NON FINAL ACTION MAILED

STPP Information on status: patent application and granting procedure in general

Free format text: RESPONSE TO NON-FINAL OFFICE ACTION ENTERED AND FORWARDED TO EXAMINER

STPP Information on status: patent application and granting procedure in general

Free format text: NOTICE OF ALLOWANCE MAILED -- APPLICATION RECEIVED IN OFFICE OF PUBLICATIONS

STPP Information on status: patent application and granting procedure in general

Free format text: PUBLICATIONS -- ISSUE FEE PAYMENT VERIFIED

STCF Information on status: patent grant

Free format text: PATENTED CASE